ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
Meeting Spotlight
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
Latest Magazine Issues
Jul 2024
Jan 2024
Latest Journal Issues
Nuclear Science and Engineering
August 2024
Nuclear Technology
Fusion Science and Technology
Latest News
ARPA-E announces $40 million to develop transmutation technologies for UNF
The Department of Energy’s Advanced Research Projects Agency–Energy (ARPA-E) announced $40 million in funding to develop cutting-edge technologies to enable the transmutation of used nuclear fuel into less-radioactive substances. According to ARPA-E, the new initiative addresses one of the agency’s core goals as outlined by Congress: to provide transformative solutions to improve the management, cleanup, and disposal of radioactive waste and spent nuclear fuel.
Advances in Thermal Hydraulics (ATH 2022)
Technical Session
Wednesday, June 15, 2022|3:15–5:00PM PDT|Redondo
Session Chair:
Nolan Goth (ORNL)
Alternate Chair:
Franklin Curtis (ORNL)
Session Organizer:
W. David Pointer
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Investigation of Point-Contact Strategies for CFD Simulations of Pebble Bed Reactor Cores
Nolan Goth (ORNL), Thien Duy Nguyen (ORNL), W. David Pointer (ORNL)
Paper
Design and CFD Analysis of Printed Circuit Steam Generator for High-Temperature Gas-Cooled Reactor Applications
Chengqi Wang (Univ. Michigan), Xiaodong Sun (Univ. Michigan)
Testing of a Large Scale RCCS Operating at Two-Phase Accident Conditions
Q. Lv (ANL), D. Lisowski (ANL), M. Jasica (ANL), Z. Ooi (ANL), A. Kraus (ANL), R. Hu (ANL), M. Farmer (ANL)
TRISO Transient Analysis: Systematic Comparison of RELAP and BISON Predictions for HTGR RIA Simulations
Carlotta G. Ghezzi (Univ. Tennessee., Knoxville), Robert F. Kile (Univ. Tennessee., Knoxville), Nicholas R. Brown (Univ. Tennessee., Knoxville)
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